References
- Tanaka K, Miwa S, Sato I, et al. Effects of interaction between molten zircaloy and irradiated MOX fuel on the fission product release behavior. J Nucl Sci Technol. 2014;51:876–885.
- Ishimi A, Katsuyama K, Maeda K, et al. Upgrading of X-ray CT technology for analyses of irradiated FBR MOX fuel. J Nucl Sci Technol. 2012;49:1144–1155.
- Minerbo GN, Sanderson JG. Reconstruction of a source from a few (2 or 3) projections [ART, CART, and MART, based on algebraic reconstruction technique; in FORTRAN]. Los Alamos (NM): Los Alamos Scientific Laboratory; 1977. ( DOE publication; no. LA-6747-MS).
- Walker CT, Bagger C, Mogensen M. Observations on the release of cesium from UO2 fuel. J Nucl Mater. 1996;240:32–42.
- Iglesias FC, Lewis BL, Reid PJ, et al. Fission product release mechanisms during reactor accident conditions. J Nucl Mater. 1999;270:21–38.
- Lewis BJ, Dickson R, Iglesias FC, et al. Overview of experimental programs on core melt progression and fission product release behavior. J Nucl Mater. 2008;380:126–143.
- Hidaka A. Outcome of VEGA program on radionuclide release from irradiated fuel under severe accident conditions. J Nucl Sci Technol. 2011;48(1):85–102.
- Johansson B. The boiling points of the rare earth metals. J Phys F Metal Phys. 1975;5:1241–1247.
- Grossman LN, Lewis JE, Rooney DM. The system UO2–EU2O3 at high temperatures. J Nucl Mater. 1967;21:302–309.
- Kleykamp H. The chemical state of the fission products in oxide fuels. J Nucl Mater. 1985;131:221–246.
- Krishnan RV, Panneerselvam G, Antony MP, et al. Solubility studies and thermal expansion coefficient of uranium–lanthanum mixed oxide system. J Nucl Mater. 2010;403:25–31.
- Ploetz GL, Krystyniak CW, Dumas HE. Sintering characteristics of rare-earth oxides. J Am Ceram Soc. 1958;41(12):551–554.
- Curtis CE, Tharp AG. Ceramic properties of europium oxide. J Am Ceram Soc. 1959;42(3):151–156.
- Adachi G, Imanaka N. The binary rare earth oxides. Chem Rev. 1998;98(4):1479–1514.
- Hofmann P, Kerwin-peck D, Nikolopoulos P. Explanation of the UO2/zircaloy-4 reaction layer sequence in terms of the total interfacial energy of the system. J Nucl Mater. 1984;124:114–119.
- Wilhelm AN, Garcia EA. Simulation of the kinetics of the UO2 dissolution by molten zircaloy-4 between 1950 and 2250°C. J Nucl Mater. 1988;158:143–158.
- Hofmann P. Current knowledge on core degradation phenomena, a review. J Nucl Mater. 1999;270:194–211.